EN IEC 60964:2019/AC:2019-08
(Corrigendum)Nuclear power plants - Control rooms - Design
- BACK
- 01-Aug-2019
- 27.120.20
- CLC/TC 45AX
Nuclear power plants - Control rooms - Design
Kernkraftwerke - Warten - Auslegung
Centrales nucléaires de puissance - Salles de commande - Conception
Jedrske elektrarne - Nadzorne sobe - Zasnova - Popravek AC
General Information
Relations
Standards Content (Sample)
SLOVENSKI STANDARD
SIST EN IEC 60964:2019/AC:2019
01-oktober-2019
Jedrske elektrarne - Nadzorne sobe - Zasnova - Popravek AC
Nuclear power plants - Control rooms - Design
Kernkraftwerke - Warten - Auslegung
Centrales nucléaires de puissance - Salles de commande - Conception
Ta slovenski standard je istoveten z: EN IEC 60964:2019/AC:2019-08
ICS:
27.120.20 Jedrske elektrarne. Varnost Nuclear power plants. Safety
SIST EN IEC 60964:2019/AC:2019 en
2003-01.Slovenski inštitut za standardizacijo. Razmnoževanje celote ali delov tega sta
...
This May Also Interest You
See the scope of IEC 62988:2018. Adoption of IEC 62988:2018 is to be done without modification.
- Standard21 pagesEnglish languagesale 10% offe-Library read for×1 day
- 18-Aug-2022
- 27.120.20
- CLC/TC 45AX
IEC 60987:2021 provides requirements and recommendations for the hardware aspects of I&C systems whatever the technology and applies for all safety classes in a graded manner (as defined by IEC 61513). The requirements defined within this document guide, in particular, the selection of pre-existing components, hardware aspects of system detailed design and implementation and equipment manufacturing. This third edition cancels and replaces the second edition published in 2007. This edition includes the following significant technical changes with respect to the previous edition: a) Title modified; b) Take account of the fact that hardware requirements apply to all I&C technologies, including conventional hardwired equipment, programmable digital equipment or by using a combination of both types of equipment; c) Align the standard with the new revisions of IAEA documents SSR-2/1, which include as far as possible an adaptation of the definitions; d) Replace, as far as possible, the requirements associated with standards published since the edition 2.1, especially IEC 61513, IEC 60880, IEC 62138, IEC 62566 and IEC 62566‑2; e) Review the existing requirements and update the terminology and definitions; f) Extend the scope of the standard to all hardware (computerized and non-computerized) and to all safety classes 1, 2 and 3; g) Complete, update the IEC and IAEA references and vocabulary; h) Check possible impact of other IAEA requirements and recommendations considering extension of the scope of SC 45A; i) Highlight the use of IEC 62566 and IEC 62566-2 for HPD development; j) Introduce specific activities for pre-existing items (selection, acceptability and/or mitigation); k) Introduce clearer requirements for electronic module-level design, manufacturing and control; l) Complete reliability assessment methods; m) Introduce requirements when using automated tests or control activities; n) Complete description of manufacturing control activities (control process, assessment of manufactured equipment, preservation of products); o) Define and ensure the inclusion of a graded approach for dealing with the 3 different classes of equipment and related requirements.
- Standard53 pagesEnglish languagesale 10% offe-Library read for×1 day
- 16-Sep-2021
- 27.120.20
- CLC/TC 45AX
This document presents the requirements for the on-site emergency response facilities (referred to hereinafter as the “ERF”) which are to be used in case of incidents or accidents occurring on the associated Nuclear Power Plant (NPP). The ERF consists of the Emergency Response Centre (ERC), the Technical Support Centre (TSC) and the Operational Support Centre (OSC), as shown in Figure 1. It establishes requirements for the ERF features and ERF I&C equipment to: • coordinate on-site operational efforts with respect to safety and radioprotection; • optimize the design in terms of environment control, lighting, power supplies and access control of the ERF; • enhance the identification and resolution of potential conflicts between the traditional operational means and emergency means (MCR/SCR and ERF, operating staff and emergency teams, operational procedures and emergency procedures); • aid the identification and the enhancement of the potential synergies between the traditional operational means and emergency means. This document is intended for application to new nuclear power plants whose conceptual design is initiated after the publication of this document, but it may also be used for designing and implementing ERF in existing nuclear power plants or in any other nuclear facility. Detailed equipment design is outside the scope of this document. This document does not define the situations (reactor plant conditions, hazards and magnitudes of hazards) leading to mobilisation of emergency response teams and activation / use of the ERF. These aspects are usually addressed in the NPP Emergency Plan. However, the need for consistency of the ERF design and operation with the NPP Emergency Plan is within scope.
- Standard29 pagesEnglish languagesale 10% offe-Library read for×1 day
- 15-Jul-2021
- 27.120.20
- CLC/TC 45AX
IEC 62855 provides the electrotechnical engineering guidelines for analysis of AC and DC electrical power systems in nuclear power plants (NPPs) in order to demonstrate that the power sources and the distribution systems have the capability for safe operation and shut down of the NPP, bringing it to a controlled state after an anticipated operational occurrence or accident conditions and finally reaching a safe state. The analytical studies discussed in this document provide assurance that the design bases are satisfied to meet their functional requirements under the conditions produced by the applicable design basis events. The studies provide assurance that the electrical power system is capable of supporting safety functions during all required plant conditions. NOTE The safety functions are described in IAEA Specific Safety Requirements SSR-2/1 related to the design of the nuclear power plants.. Analytical studies validate the robustness and adequacy of design margins and demonstrate the capability of electrical power systems to support plant operation for normal, abnormal, degraded and accident conditions. The analyses are used to verify that the electrical power system can withstand minor disturbances and that the consequences of major disturbances or failures do not degrade the capability of the electrical power systems to support safe shutdown of the plant and maintain the plant in shutdown condition. The analyses are performed with one or more of • simulation tools (software and hardware) that have been verified and validated, • hand calculations, and • tests. This document provides guidance on the types of analyses required to demonstrate that the plant's auxiliary power system can perform the required safety functions. This document does not provide specific details on how the analysis should be conducted. This document does not cover digital controllers (such as controllers for rectifiers, inverters, sequencers and electrical protection devices) used in electrical power systems. IEC 61513 gives recommendations that apply to the electronic controls and protective elements of the electrical power systems. This document does not include environmental conditions (i.e. temperature, humidity, etc.) or external events (seismic, flooding, fire, high energy electromagnetic pulse, etc.) that may impact equipment sizing or protection requirements. The external events lightning and geomagnetic storms are included. This document does not cover additional or unique requirements for stand-alone power system, such as power supplies for security measures in NPPs. Pertinent clauses of this document may be used as a guideline for such systems. Redundancy in the power system design can increase the availability of electrical power to critical plant equipment. Performing a probabilistic risk assessment (PRA) is a method of assessing system availability and optimizing design for high reliability. This document does not cover improving the reliability of NPP electrical power systems using statistical or diverse and redundant schemes. Requirements for safeguards of personnel involved with installation, maintenance and operation of electrical systems and general personal safety are outside the scope of this document. General guidance for lightning protection of equipment is provided in relevant clauses of this document. This document is intended to be used: • for verification of the design of new nuclear power plants, • for demonstrating the adequacy and impact of major modifications of electrical power systems in operating nuclear power plants, and • where there is a requirement to assess and establish operating limits and constraints for existing plants. Pertinent parts of this document can be used as guidance for decommissioning stages.
- Standard60 pagesEnglish languagesale 10% offe-Library read for×1 day
- 15-Jul-2021
- 27.120.20
- CLC/TC 45AX
This part of IEC/IEEE 62582 contains methods for condition monitoring of organic and polymeric materials in instrumentation and control cables using insulation resistance measurements in the detail necessary to produce accurate and reproducible results during simulated accident conditions. It includes the requirements for the measurement system and measurement procedure, and the reporting of the measurement results. NOTE Measurement of insulation resistance during simulated accident conditions with the aim of determining the lowest value during the accident in order to assess cable performance involves special requirements given in this document. Methods for measurement under stable (non-accident) conditions are available in other international standards, e.g. IEC 62631-3-3. The different parts of the IEC/IEEE 62582 series are measurement standards, primarily for use in the management of ageing in initial qualification and after installation. IEC/IEEE 62582- 1 includes requirements for the application of the other parts of the IEC/IEEE 62582 series and some elements which are common to all methods. Information on the role of condition monitoring in qualification of equipment important to safety is found in IEC/IEEE 60780-323.
- Standard27 pagesEnglish languagesale 10% offe-Library read for×1 day
- 15-Jul-2021
- 27.120.20
- CLC/TC 45AX
This document establishes, for nuclear power plants2, a method of assignment of the functions specified for the plant into categories according to their importance to safety. Subsequent classification of the I&C and electrical power systems performing or supporting these functions, based on the assigned category, then determines relevant design criteria. The design criteria, when applied, ensure the achievement of each function in accordance to its importance to safety. In this document, the criteria are those of functionality, reliability, performance, environmental qualification (e.g. seismic) and quality assurance (QA). This document is applicable to: - the functions important to safety that are performed by I&C systems and supported by electrical power systems (categorization of I&C functions), - the I&C systems that enable those functions to be implemented (classification of I&C systems), - the electrical power systems that support those functions (classification of electrical power systems). The systems under consideration provide automated protection, closed or open loop control, information to the operating staff, and electrical power supply to systems. These systems keep the NPP conditions inside the safe operating envelope and provide automatic actions, or enable manual actions, that prevent or mitigate accidents, or that prevent or minimize radioactive releases to the site or wider environment. The I&C and electrical power systems that fulfil these roles safeguard the health and safety of the NPP operators and the public. This document follows the general principles given in IAEA Safety Requirement SSR-2/1 and Safety Guides SSG-30, SSG-34 and SSG-39, and it defines a structured method of applying the guidance contained in those codes and standards to the I&C and electrical power systems that perform functions important to safety in a NPP. This document is read in association with the IAEA guides together with IEC 61513 and IEC 63046 in implementing the requirements of the IEC 61508 series. The overall classification scheme of structures, systems and components for NPPs can be summarized as follows by Figure 1.
- Standard43 pagesEnglish languagesale 10% offe-Library read for×1 day
- 15-Jul-2021
- 27.120.20
- CLC/TC 45AX
See the scope of IEC 63046:2020. Adoption of IEC 63046:2020 is to be done without modification.
- Standard91 pagesEnglish languagesale 10% offe-Library read for×1 day
- 20-May-2021
- 27.120.20
- CLC/TC 45AX
See the scope of IEC/IEEE 60980-344:2020. Adoption of IEC/IEEE 60980-344:2020is to be done without modification.
- Standard85 pagesEnglish languagesale 10% offe-Library read for×1 day
- 22-Apr-2021
- 27.120.10
- 27.120.20
- CLC/TC 45AX
See the scope of IEC 62566-2:2020. Adoption of IEC 62566-2:2020 is to be done without modification.
- Standard61 pagesEnglish languagesale 10% offe-Library read for×1 day
- 26-Nov-2020
- 27.120.20
- CLC/TC 45AX
IEC 62003:2020 establishes requirements for electromagnetic compatibility testing of instrumentation, control, and electrical equipment supplied for use in systems important to safety at nuclear power plants and other nuclear facilities. The document lists the applicable IEC standards (principally the IEC 61000 series) which define the general test methods, and provides the necessary application-specific parameters and criteria to ensure that nuclear safety requirements are met. This second edition cancels and replaces the first edition published in 2009. This edition includes the following significant technical changes with respect to the previous edition: a) title modified. b) expand the scope to encompass Electromagnetic Magnetic Compatibility (EMC) considerations for electrical equipment. c) provide guidance for addressing the use of wireless technology. d) enhance the description of the electromagnetic environment to provide clarification when selecting custom test levels or for test exemptions. e) include example information to be contained within an EMC test plan. f) provide guidance for characterization of the electromagnetic environment at the point of installation within a nuclear facility.
- Standard42 pagesEnglish languagesale 10% offe-Library read for×1 day
- 17-Sep-2020
- 27.120.20
- CLC/TC 45AX
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.